Overall test operation of KT-1 tokamak has been done with the modified power supplies and constructed plasma position feedback control system. The achieved plasma parameters of KT-1 are Ip (plasma current) > 15 kA (9ms) and Td (plasma current sustaining time) > 12 ms (7.5 kA) until now. Instrumentations for the carbonization/boronization are also equipped and applied to the first boronization of invessel components of KT-1 tokamak. As a preliminary treatment of the 1st wall of tokamak vacuum torus, RG discharge cleaning has been done. Plasma qualities have been improved by discharge cleaning. In addition, helicon plasma device is designed succeeding exploitation of the first wall conditioning program which are all for the development of conditioning technology of 1st wall facing the plasma. As a part of the development program on the plasma monitoring technologies, conceptual design study on the FIR interferometer- polarimeter is accomplished. Parallel to these experimental activities, an effort has been made in designing the operating scenario of poloidal field system of KT-2 tokamak. (Author).
Lee, Kwang Won; Hwang, Chul Kew; In, Sang Ryul; Kim, Sung Kyu; Oh, Byung Hoon; Jeong, Seung Ho; Hong, Bong Guen; Yoon, Jae Sung; Yoon, Byung Joo; Song, Woo Sup;  Park, Byung Ho;  Park, Byung Ki; Lyu, Ji Myung 
- Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
- Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)
- Seoul National Univ., Seoul (Korea, Republic of)